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EAY 211985 MEMORANDUM'FOR:
H. Denton, NRR D. Eisenhut, NRR G. Edison, TOSB, NRR H. Thompson, DL F. Miraglia, DL T. Novak, DL W. Russell, Acting Director, DHFS J. Knight, Acting Director, DE R. Bernero, DSI
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T. Speis, DST B. Snyder, TMIPO, NRR G. Holahan, ORAB G. Lainas, DL D. Crutchfield, DL THRU:
George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing FROM:
Hans Schierling, Project Manager Licensing Branch No. 3 Division of Licensing
SUBJECT:
DAILY HIGHLIGHT Diablo Canyon Unit 2
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Fuel loading was completed May 15. Currently the vessel head i) being tensioned down.
The Unit is expected to go critical on about July 7 and will be ready for power accession by July 17.
Unit 1 Since May 18 the Unit experienced three separate reactor trips, all of which apparently due to failures in the power supply system for instruments in the control room. The licensee is evaluating the root cause(s). The Unit is currently at 20 percent power.
wG Cadj t'2-g Hans Schierling, Project Manager Licensing Branch No. 3 Division of Licensing
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MEMORANDUM'FOR:
H. Denton, NRR 3
D. Eisenhut NRR G. Edison, TOSB, NRR H. Thompson, DL F. Miraglia, DL T. Novak, DL W. Russell, Acting Director, DHFS J. Knight, Acting Director, DE R. Bernero, DSI T. Speis, DST B. Snyder, TMIPO, NRR G. Holahan, ORAB G. Lainas, DL D. Crutchfield, DL k
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George W. Knighton, Chief Licensing Branch No. 3 i:
Y Division of Licensing FROM:
Hans Schierling, Project Manager Licensing Branch No. 3 Division of Licensing
SUBJECT:
DAILY HIGHLIGHT Diablo Canyon Unit 2_
N Fuel loading was completed May 15. Currently the vessel head is being tensioned down. The Unit is expected to go critical on about July 7 and will be ready for power accession by July 17.
Unit 1 l
Since May 18 the Unit experienced three separate reactor trips, all of which apparently due to failures in the power supply system for instruments in the control room.
The licensee is evaluating the root cause(s). The Unit is currently at 20 percent power.
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{ F MEMORANDUM FOR: Hugh L. Thompson, Director Division of Licensing i
FROM:
James P. Knight, Acting Director Division of Engineering SOBJECT:
BOARD NOTIFICATION REGARDING REPORT ON REACTOR COOLANT PUMP SHAFT SEAL BEHAVIOR DURING STATION BLACK 0UT (APRIL 1985 NUREG/CR-4077)
References:
- 1) Memo from D. Eisenhut to the Comission dated September 21, 1983, Board Notification Regarding Westinghouse Reactor Coolant Pump Seals (BN-83-139)
- 2) Memo from D. Eisenhut to the Comission dated i
April 19, 1984, Board Notification Regarding Westinghouse Reactor Coolant Pump Seals (BN-84-076) i
- 3) Memo from D. Eisenhut to the Commission dated June 29, 1984, Board Notification Regarding Westinghouse Reactor Coolant Pump Seals (BN-84-123)
Board Notification BN-84-076 made the boards aware of the reactor coolant pump (RCP) seal test program at Atomic Energy of Canada Limited (AECL) and the preliminary test results which indicated failures of certain secondary seal materials at conditions knich could be expected to occur during extended station blackout. Board notifications BN-83-139 regarding results from a Westinghouse test program and BN-84-123.regarding French RCP seal testing, provided information from other sources regarding possible reactor coolant pump seal failures.
The RCP seal test program at AECL is now complete and the final results have been published in NUREG/CR-4077, Reactor Coolant-Pump Shaft Seal Behavior During Station Blackout, dated April 1985. The report suggests several failure modes which could result in large leakage through RCP seals during extended station blackout. The report gives detailed information on the test program and the implications of the results, including identification of secondary seals in present use which may be likely to fail in a station blackout.
Contact:
J. Jackson Ext. 27930 MN h
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MAY 24 1985 Hugh L. Thompson The Westinghouse Owners Group (WOG) has acknowledged the possible failure of a secondary 0-ring seal material (Parker E515-80)'used in Westinghouse RCP seal assemblies and has comitted to the replacement of the 0-rings presently This commitment is outlined in a used in the RCPs of Westinghouse plants.
letter (OG-142) from J. J. Sheppard, Chairman of WOG, to Harold Denton dated January 3, 1984.
We recommend board notification of this additional informaton as it relates to the previous referenced board notifications and industry wide notification through an IE bulletin or information notices.
N ares P. Knig t, Acting Director
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ivision of Engineering
Contact:
J. Jackson Ext. 27930
Enclosures:
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1.
WOG Letter OG-142 l
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CP&L Carolina Power & Light Company OG-142 January 3, 1984 Mr. Harold Denton Office of Nuclear Reactor. Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Westinghouse Owners Group Reactor Coolant Pump Seal Integrity Program Dear Mr. Dentoni Because it has been some time since the Westinghouse Owners Group (WOG) last met with the Nuclear Regulatory Commission (NRC) to discuss the subject program and since there have recently been several significant developments, we believe it appropriate to advise you of the status of the program. The purpose then of this letter is to provide that status to you:
1.
Confirmation of WOG Analyses We understand that independent analyses performed for the NRC by Energy Technology Engineering Center (ETEC) confirm analyses performed by Westinghouse for the WOG, and that these results have been reported to the NRC. Tnat is, the best estimate leakage flow under the conditions of the loss of all seal cooling is approximately 20 gpm per pump.
2.
Secondary Seal Tests A program of testing of 0-rings and channel seals at the Chalk River National Laboratory of Atomic Energy of Canada, Ltd. (AECL) is approximately 50% complete. All of the 0-ring tests have been completed. Channel seal tests are expected to be completed by early January 1985.
The results to-date confirm the results of the earlier NRC sponsored tests. 0-rings of two materials (Parker E740-75 and Seals Eastern 7228-75) have been tested at conditions more severe than expected to exist in the RCP seal system during a loss of all seal cooling event and have retained their integrity for 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. At the extreme conditions, these materials proved to be superior to the Parker E515-80 material which is comparable to the material currently in use.
411 Fayetteville Street
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